JPH0652318B2 - Manufacturing method of nuclear fuel sintered body - Google Patents
Manufacturing method of nuclear fuel sintered bodyInfo
- Publication number
- JPH0652318B2 JPH0652318B2 JP63008109A JP810988A JPH0652318B2 JP H0652318 B2 JPH0652318 B2 JP H0652318B2 JP 63008109 A JP63008109 A JP 63008109A JP 810988 A JP810988 A JP 810988A JP H0652318 B2 JPH0652318 B2 JP H0652318B2
- Authority
- JP
- Japan
- Prior art keywords
- sintering
- zone
- high temperature
- nuclear fuel
- temperature
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
Links
- 239000003758 nuclear fuel Substances 0.000 title claims description 13
- 238000004519 manufacturing process Methods 0.000 title claims description 6
- 238000005245 sintering Methods 0.000 claims description 53
- 238000000034 method Methods 0.000 claims description 12
- 239000000843 powder Substances 0.000 claims description 11
- 238000010438 heat treatment Methods 0.000 claims description 10
- 239000002994 raw material Substances 0.000 claims description 10
- 229910052724 xenon Inorganic materials 0.000 claims description 6
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 claims description 6
- 238000000465 moulding Methods 0.000 claims description 4
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 7
- 238000009792 diffusion process Methods 0.000 description 7
- 229910052750 molybdenum Inorganic materials 0.000 description 7
- 239000011733 molybdenum Substances 0.000 description 7
- 239000008188 pellet Substances 0.000 description 7
- 238000007796 conventional method Methods 0.000 description 5
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 4
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 4
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 3
- 239000011449 brick Substances 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 2
- 239000000470 constituent Substances 0.000 description 2
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(iii) oxide Chemical compound [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 2
- 239000011810 insulating material Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- AFCARXCZXQIEQB-UHFFFAOYSA-N N-[3-oxo-3-(2,4,6,7-tetrahydrotriazolo[4,5-c]pyridin-5-yl)propyl]-2-[[3-(trifluoromethoxy)phenyl]methylamino]pyrimidine-5-carboxamide Chemical compound O=C(CCNC(=O)C=1C=NC(=NC=1)NCC1=CC(=CC=C1)OC(F)(F)F)N1CC2=C(CC1)NN=N2 AFCARXCZXQIEQB-UHFFFAOYSA-N 0.000 description 1
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 239000011230 binding agent Substances 0.000 description 1
- 150000001768 cations Chemical class 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 229910001938 gadolinium oxide Inorganic materials 0.000 description 1
- 229940075613 gadolinium oxide Drugs 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 229910001404 rare earth metal oxide Inorganic materials 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- ZCUFMDLYAMJYST-UHFFFAOYSA-N thorium dioxide Chemical compound O=[Th]=O ZCUFMDLYAMJYST-UHFFFAOYSA-N 0.000 description 1
- 229910003452 thorium oxide Inorganic materials 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Powder Metallurgy (AREA)
- Tunnel Furnaces (AREA)
Description
【発明の詳細な説明】 〔発明の技術分野〕 本発明は、核燃料焼結体の製造方法に関する。TECHNICAL FIELD OF THE INVENTION The present invention relates to a method for producing a nuclear fuel sintered body.
原子炉に使用されている核燃料は、二酸化ウラン、酸化
プルトニウム入り二酸化ウラン等の成分から構成され、
通常はこれら酸化物を成形、焼結して得られる焼結ペレ
ットとして用いられる。また、上記核燃料構成成分とし
ては、さらに、中性子吸収物質として酸化ガドリニウム
（Ｇｄ２Ｏ３）等の希土類酸化物が添加される。Nuclear fuel used in nuclear reactors is composed of components such as uranium dioxide and plutonium oxide-containing uranium dioxide.
Usually, it is used as a sintered pellet obtained by molding and sintering these oxides. Further, as the nuclear fuel constituent, a rare earth oxide such as gadolinium oxide (Gd 2 O 3 ) is added as a neutron absorbing substance.
ところで、このような核燃料粉末を成形し焼結する場
合、通常、１６００〜１８００℃の還元雰囲気（たとえ
ばＨ２）が使用される。焼結速度は焼結温度に比例する
ので、１８００℃以上の温度で焼結すれば、それだけ短
時間で焼結が完了する。ところが、現在一般的に使用さ
れている核燃料酸化物焼結用の炉は、モリブデンを発熱
体とし、アルミナレンガを断熱材とした連続式トンネル
炉が主流である。したがって、耐熱性の観点から１８０
０℃以上の高温度を維持することは困難であり、したが
って１８００℃以下の焼結温度で長時間の焼結が必要と
なる。このようにモリブデン発熱体、アルミナレンガ断
熱材で構成される連続式トンネル炉は、１８００℃以上
の高温度にできないことと、輻射および熱伝導により周
囲から成形体に熱が供給される為にエネルギーのロスが
大きいこと、の２つが欠点である。By the way, when molding and sintering such a nuclear fuel powder, a reducing atmosphere (for example, H 2 ) of 1600 to 1800 ° C. is usually used. Since the sintering rate is proportional to the sintering temperature, if the sintering is performed at a temperature of 1800 ° C. or higher, the sintering will be completed in a shorter time. However, the most commonly used nuclear fuel oxide sintering furnace is a continuous tunnel furnace in which molybdenum is used as a heating element and alumina brick is used as a heat insulating material. Therefore, from the viewpoint of heat resistance, 180
It is difficult to maintain a high temperature of 0 ° C. or higher, and therefore, sintering at a sintering temperature of 1800 ° C. or lower for a long time is required. In this way, a continuous tunnel furnace composed of a molybdenum heating element and an alumina brick heat insulating material cannot be heated to a high temperature of 1800 ° C or higher, and heat is supplied to the molded body from the surroundings by radiation and heat conduction, which causes energy loss. There are two drawbacks: the loss is large.
本発明は上述した点に鑑みてなされたものであり、エネ
ルギーコストの低減化が図られた核燃料焼結体の製造方
法を提供することを目的としている。The present invention has been made in view of the above points, and an object of the present invention is to provide a method for manufacturing a nuclear fuel sintered body in which energy cost is reduced.
本発明に係る核燃料焼結体の製造方法は、核燃料原料粉
末を成形し、焼結する方法において、原料粉末の成形体
を予め、１８００℃以下、好ましくは１６００〜２００
０℃の還元性雰囲気中において短時間に焼結する工程を
含むことを特徴としている。The method for producing a nuclear fuel sintered body according to the present invention is a method of compacting and sintering a nuclear fuel raw material powder, wherein the raw material powder compact is preliminarily 1800 ° C. or less, preferably 1600 to 200.
It is characterized by including a step of sintering in a reducing atmosphere at 0 ° C. for a short time.
以下、本発明をさらに詳細に説明する。 Hereinafter, the present invention will be described in more detail.
成形体の製造 本発明で用いられる核燃料粉末としては、二酸化ウラン
その他の酸化ウラン、酸化プルトニウム、酸化トリウム
等の１種または２種以上に、さらに中性子吸収物質とし
て酸化ガドリニウムを加えた混合物が用いられ得る。こ
れら原料粉末の粒径は、混合前において、約１０〜１５
００μｍ程度の範囲が好ましい。Manufacture of Molded Body As the nuclear fuel powder used in the present invention, a mixture obtained by adding gadolinium oxide as a neutron absorbing substance to one or more kinds of uranium dioxide and other uranium oxide, plutonium oxide, thorium oxide and the like is used. obtain. The particle size of these raw material powders is about 10 to 15 before mixing.
The range of about 00 μm is preferable.
また、上記原料粉末には、成形性その他の性状を向上さ
せるために、必要に応じてバインダーを添加してもよ
い。In addition, a binder may be added to the raw material powder as needed in order to improve moldability and other properties.
次いで、上記原料粉末を常法に従い、所望形状の成形機
の金型中に装入し、例えば０．５〜５ton/cm2程度の圧
力で成形して、４０〜６０％ＴＤ（理論密度の４０％〜
６０％、理論密度は二酸化ウランの場合１０．９５ｇ／
cm2）の成形体を得る。Then, the above-mentioned raw material powder is charged into a mold of a molding machine having a desired shape according to a conventional method, and is molded at a pressure of, for example, about 0.5 to 5 ton / cm 2 to obtain 40 to 60% TD (theoretical density 40% ~
60%, theoretical density is 10.95 g / in case of uranium dioxide
A molded body of cm 2 ) is obtained.
焼結 本発明においては、上記原料粉末の成形体を予め、１８
００℃以下、好ましくは１６００〜１８００℃の還元性
雰囲気で予備加熱した後、１８００℃以上、好ましくは
１８００〜２０００℃以上の還元性雰囲気中において短
時間に焼結する工程を含むことを特徴としている。Sintering In the present invention, a molded body of the above raw material powder is previously
The method is characterized by including a step of preheating in a reducing atmosphere at 00 ° C or lower, preferably 1600 to 1800 ° C, and then sintering in a reducing atmosphere at 1800 ° C or higher, preferably 1800 to 2000 ° C or higher for a short time. There is.
本発明における焼結工程は、予備加熱ゾーンと高温焼結
ゾーンとから構成される連続焼結炉によって行なわれ得
る。The sintering process in the present invention can be performed by a continuous sintering furnace composed of a preheating zone and a high temperature sintering zone.
第１図に、このような連続トンネル焼結炉の一例を概略
図で示す。すなわち、本図に示すように焼結炉は、基本
的には、予備加熱もしくは昇温ゾーンＡと高温焼結ゾー
ンＢならびに降温ゾーンＣから構成され、昇温ゾーンＡ
および降温ゾーンＣには、加熱手段としてたとえばモリ
ブデンヒーター１が設けられ、高温焼結ゾーンＢには加
熱源としてキセノンランプ２が設けられている。成形体
３は、スキッド４に搭載されて炉内を連続的に移動す
る。FIG. 1 schematically shows an example of such a continuous tunnel sintering furnace. That is, as shown in the figure, the sintering furnace basically comprises a preheating or temperature raising zone A, a high temperature sintering zone B and a temperature lowering zone C.
A molybdenum heater 1 is provided as a heating means in the temperature lowering zone C, and a xenon lamp 2 is provided as a heating source in the high temperature sintering zone B. The molded body 3 is mounted on the skid 4 and continuously moves in the furnace.
このように、高温焼結ゾーンＢは、加熱源がキセノンラ
ンプからなり、昇温ゾーンＡで予備加熱された成形体を
該高温焼結ゾーンＢ中で、好ましくは１８００〜２００
０℃の温度下において、好ましくは、１０〜３０分間焼
結する。このときの焼結温度の限定理由は次の通りであ
る。As described above, in the high temperature sintering zone B, the heating source is a xenon lamp, and the molded body preheated in the temperature rising zone A is preferably heated in the high temperature sintering zone B in the range of 1800 to 200.
Sintering is preferably performed at a temperature of 0 ° C. for 10 to 30 minutes. The reason for limiting the sintering temperature at this time is as follows.
通常の還元雰囲気炉では１８００℃までしか温度を上げ
ることができない。この理由は使用しているアルミナレ
ンガがこれ以上の温度に耐えることができないからであ
る。本発明では成形体のみを加熱する方法であるので１
８００℃の高温度で焼結可能となる。１８００℃以上の
高温度であるならば、本発明の目的は達せられるが、２
０００℃以上の温度になるとＵＯ２の蒸発が激しくな
り、好ましくない。In a normal reducing atmosphere furnace, the temperature can be raised only up to 1800 ° C. The reason for this is that the alumina bricks used cannot withstand higher temperatures. In the present invention, since only the molded body is heated, 1
It becomes possible to sinter at a high temperature of 800 ° C. If the temperature is higher than 1800 ° C., the object of the present invention can be achieved.
At a temperature of 000 ° C. or higher, the evaporation of UO 2 becomes severe, which is not preferable.
前記予備加熱ゾーン中においては、原料成形体を予め１
６００〜１８００℃に加熱することが好ましい。また、
この場合の昇温速度は、１０〜１５度／分の範囲が好ま
しい。１０℃未満では、プッシャー形式の焼結炉である
ため、予備加熱域に滞在する時間が長くなり、予備加熱
としては過剰なエネルギーを与えることになる。したが
って、本発明の目的であるエネルギーコストの低減化の
ためには好ましくない。一方、１５℃を超える温度で焼
結することは、被処理物に与える熱衝撃が多きく、微細
組織中にクラック等が発生し、このため製品に悪影響を
与える結果となる。In the preheating zone, the raw material compact is preliminarily
It is preferable to heat to 600 to 1800 ° C. Also,
In this case, the heating rate is preferably in the range of 10 to 15 degrees / minute. If the temperature is lower than 10 ° C., since it is a pusher type sintering furnace, the staying time in the preheating zone becomes long, and excessive energy is applied as preheating. Therefore, it is not preferable for the purpose of the present invention to reduce the energy cost. On the other hand, sintering at a temperature higher than 15 ° C. causes a large amount of thermal shock on the object to be processed, and cracks or the like are generated in the fine structure, which adversely affects the product.
次いで、上記焼結後、焼結体を、降温ゾーンＣで徐々に
冷却するが、このときの降温速度は、１０〜１５度／分
が好ましい。Next, after the above sintering, the sintered body is gradually cooled in the temperature lowering zone C, and the temperature lowering rate at this time is preferably 10 to 15 degrees / minute.
第２図は、上記の様な焼結温度プロファイルの一例を示
すグラフである。FIG. 2 is a graph showing an example of the above sintering temperature profile.
得られた焼結体は、例えば所望の直径に研削し、これを
燃料被覆管中に装填し不活性ガスに置換して封入し燃料
棒としそれらを集めて燃料集合体として原子炉の運転に
供する。The obtained sintered body is ground, for example, to a desired diameter, charged in a fuel cladding tube, replaced with an inert gas and sealed, and made into fuel rods which are collected and used as a fuel assembly for the operation of a nuclear reactor. To serve.
ところで、従来の方法においては、１８００℃以上の温
度に連続式トンネル炉全体を維持するためには、炉の超
耐熱設計が必要となる。本発明のように、焼結対象ペレ
ットのみに熱エネルギーを集中することができれば、こ
のような超耐熱設計が不要となる。本発明においては、
ペレットを平板上に並べて、上下部よりキセノンランプ
等を使用したイメージ形式により、ペレットに熱エネル
ギーを集中させることにより上記短時間高温焼結を実施
することができる。平板上には多数列にわたってペレッ
トが並んでいるので、列数に合わせたキセノンランプ等
を焼結炉の上下部に取り付け、エネルギーがペレット上
に集中されるように、それぞれのランプに反射鏡を取り
付けることもできる。また、上述したように、このイメ
ージ形式部分の前後は通常のモリブデン発熱体を使用し
た連続式トンネル炉で構成され得る。By the way, in the conventional method, in order to maintain the entire continuous tunnel furnace at a temperature of 1800 ° C. or higher, the super heat resistant design of the furnace is required. If the heat energy can be concentrated only on the pellets to be sintered as in the present invention, such super heat resistant design becomes unnecessary. In the present invention,
By arranging the pellets on a flat plate and concentrating thermal energy on the pellets from the upper and lower portions in an image format using a xenon lamp or the like, the high-temperature sintering for a short time can be performed. Since the pellets are lined up in multiple rows on a flat plate, mount a xenon lamp, etc., matching the number of rows in the upper and lower parts of the sintering furnace, and attach a reflector to each lamp so that the energy is concentrated on the pellets. It can also be attached. Further, as described above, before and after this image type portion, a continuous tunnel furnace using a normal molybdenum heating element may be used.
本発明によれば、１６００〜１８００℃の還元雰囲気で
中時間を必要とした核燃料酸化物の焼結を、１８００〜
２０００℃の温度において短時間で行なうことにより省
エネルギーを促進し、製品のコストダウンをはかること
ができる。焼結温度を上げることにより機器固有の定常
時運転電力は増加するが、焼結時間としては非常に短く
なるので、総合的に見ると、ＵＯ２の単位重量あたりの
供給エネルギーの低減化を図ることができる。According to the present invention, sintering of a nuclear fuel oxide that requires an intermediate time in a reducing atmosphere at 1600 to 1800 ° C. is performed at 1800 to
Energy saving can be promoted and the cost of the product can be reduced by carrying out at a temperature of 2000 ° C. for a short time. Increasing the sintering temperature will increase the steady-state operating power peculiar to the equipment, but the sintering time will be very short. Therefore, when viewed comprehensively, the energy supply per unit weight of UO 2 will be reduced. be able to.
たとえば、モリブデン発熱体を使用した従来の連続式ト
ンネル炉による焼結法と、上記本発明の方法に従った連
続式トンネル炉の単位ＵＯ２量あたりの消費電力量を比
較すると以上の通りである。For example, the power consumption per unit UO 2 amount of the conventional continuous tunnel furnace using a molybdenum heating element and the continuous tunnel furnace according to the method of the present invention is compared as described above. .
まず従来法による連続式トンネル炉の定常運転時の電気
容量を８０kwhとし、焼結温度を１７００℃とする。ま
ず、核燃料酸化物成形体（以下、ＵＯ２を主体にしたも
のとする）の焼結は、構成原子のうち、主として陽イオ
ンの拡散により支配される。したがって、ＵＯ２の焼結
はＵの内部拡散に支配される。１７００℃（１９７３
Ｋ）時のＵの拡散係数は、約９×１０−１６cm2/secで
ある〔Reimann,D.K.,Lundy,T.S.：J.Am.Ceram,Soc.,52,
511(1969)〕。この場合、通常１７００℃の温度で４時
間保持されて焼結が完了する。この時のＵの拡散距離は
約５×１０−６cmとなる〔「固体内の拡散」笛木和雄、
北沢宏一共沢（コロナ社）〕。First, the electric capacity during steady operation of the continuous tunnel furnace according to the conventional method is set to 80 kwh, and the sintering temperature is set to 1700 ° C. First, the sintering of the nuclear fuel oxide compact (hereinafter, mainly composed of UO 2 ) is mainly controlled by the diffusion of cations among the constituent atoms. Therefore, the sintering of UO 2 is dominated by the internal diffusion of U. 1700 ° C (1973
The diffusion coefficient of U at K) is about 9 × 10 −16 cm 2 / sec [Reimann, DK, Lundy, TS: J. Am. Ceram, Soc., 52,
511 (1969)]. In this case, the temperature is usually maintained at 1700 ° C. for 4 hours to complete the sintering. At this time, the diffusion distance of U is about 5 × 10 −6 cm [“Diffusion in solids” Kazuo Fueki,
Koichi Kitazawa Kyozawa (Corona)].
一方、２０００℃（２２７３Ｋ）でこれと同程度の拡散
距離を得る為には、２０００℃でのＵの拡散係数が約２
×１０−１４cm2/secより０．２時間となる。これらの
ことを考慮すると、スキッド１枚あたりに積みこみ可能
なＵＯ２の量は、通常の容器の1/2となるが、焼結時間
が短時間であるので、単位時間あたりのスキッドの搬出
数は通常の４倍となる。したがって、焼結ＵＯ２量は単
位時間あたり２倍となる。新考案の連続式トンネル炉の
定常運転時の電気容量は１２０kwh程度（モリブデンヒ
ーター部に６０kw、イメージ形式部分に６０kw使用す
る）であるので同一処理量時間あたり現在炉と比較して
１時間あたり２０kwの削減となる。On the other hand, in order to obtain the same diffusion distance at 2000 ° C (2273K), the diffusion coefficient of U at 2000 ° C is about 2
It is 0.2 hours from × 10 −14 cm 2 / sec. Taking these things into consideration, the amount of UO 2 that can be loaded per skid is half that of a normal container, but since the sintering time is short, the skid can be carried out per unit time. The number will be four times the usual number. Therefore, the amount of sintered UO 2 is doubled per unit time. The electric capacity of the newly devised continuous tunnel furnace during steady operation is about 120kwh (60kw for molybdenum heater part and 60kw for image type part), so 20kw per hour for the same throughput time compared to the current furnace. Will be reduced.
実施例１ ＵＯ２粉末を２ton/cm2（成形体密度 ５．３ｇ／cc）
で成形後、従来方法（１７００℃、Ｈ２雰囲気中 ４時
間焼結）と本発明（１９５０℃、Ｈ２雰囲気中２０分焼
結）とで焼結を実施した結果、両者とも９６．０％ＴＤ
の焼結密度を得て、ペレット中の微細組織も従来方法と
同様のものが得られた。Example 1 2 ton / cm 2 of UO 2 powder (molded body density 5.3 g / cc)
After being molded by, the conventional method (1700 ° C., 4 hours sintering in H 2 atmosphere) and the present invention (1950 ° C., 20 minutes sintering in H 2 atmosphere) were performed, and as a result, both were 96.0%. TD
The obtained sintered density was obtained, and the fine structure in the pellet was similar to that of the conventional method.
第１図は本発明の用いる焼結炉の一例を示す断面概念
図、第２図は焼結温度プロファイルの一例を示すグラフ
である。 １…モリブデンヒーター、２…キセノンランプ、３…成
形体、４…スキッド。FIG. 1 is a conceptual sectional view showing an example of a sintering furnace used in the present invention, and FIG. 2 is a graph showing an example of a sintering temperature profile. 1 ... Molybdenum heater, 2 ... Xenon lamp, 3 ... Molded body, 4 ... Skid.
Claims (7)
おいて、原料粉末の成形体を１８００℃以下の還元性雰
囲気予備加熱ゾーンで加熱した後、 １８００℃以上の還元性雰囲気高温焼結ゾーン中におい
て短時間に焼結する工程を含むことを特徴とする、核燃
料焼結体の製造方法。1. A method of molding and sintering a nuclear fuel raw material powder, wherein a raw material powder compact is heated in a reducing atmosphere preheating zone of 1800 ° C. or lower, and then a reducing atmosphere high temperature sintering zone of 1800 ° C. or higher. A method for producing a nuclear fuel sintered body, comprising a step of sintering in a short time.
成される連続焼結炉によって焼結が行なわれる、請求項
１の方法。2. The method of claim 1, wherein the sintering is carried out in a continuous sintering furnace consisting of a preheating zone and a high temperature sintering zone.
め１６００〜１８００℃に加熱する、請求項２の方法。3. The method according to claim 2, wherein the raw material compact is preheated to 1600 to 1800 ° C. in the preheating zone.
ンプからなり、予備加熱ゾーンで予備加熱された成形体
を該高温焼結ゾーン中で、１８００〜２０００℃の温度
下において短時間で焼結する、請求項２の方法。4. The high temperature sintering zone comprises a xenon lamp as a heating source, and a compact preheated in the preheating zone is baked in the high temperature sintering zone at a temperature of 1800 to 2000 ° C. for a short time. The method of claim 2, wherein
求項２の方法。5. The method according to claim 2, wherein the sintered body is gradually cooled after completion of the sintering.
〜３０分である、請求項２の方法。6. The heating time in the high temperature sintering zone is 10.
The method of claim 2, which is -30 minutes.
る、請求項２の方法。7. The method of claim 2, wherein only the compact is heated in the high temperature sintering zone.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63008109A JPH0652318B2 (en) | 1988-01-18 | 1988-01-18 | Manufacturing method of nuclear fuel sintered body |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63008109A JPH0652318B2 (en) | 1988-01-18 | 1988-01-18 | Manufacturing method of nuclear fuel sintered body |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01184497A JPH01184497A (en) | 1989-07-24 |
| JPH0652318B2 true JPH0652318B2 (en) | 1994-07-06 |
Family
ID=11684127
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63008109A Expired - Fee Related JPH0652318B2 (en) | 1988-01-18 | 1988-01-18 | Manufacturing method of nuclear fuel sintered body |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0652318B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4863315B2 (en) * | 2009-02-18 | 2012-01-25 | 独立行政法人日本原子力研究開発機構 | Method for producing nuclear fuel pellet for fast breeder reactor |
| JP4863313B2 (en) * | 2009-02-18 | 2012-01-25 | 独立行政法人日本原子力研究開発機構 | Method for producing nuclear fuel pellet for fast breeder reactor in fast breeder reactor cycle |
-
1988
- 1988-01-18 JP JP63008109A patent/JPH0652318B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01184497A (en) | 1989-07-24 |
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